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Effects of ion irradiation on microstructure and properties of zirconium alloysdA review
Chunguang Yan,Rongshan Wang,Yanli Wang,Xitao Wang,Guanghai Bai 한국원자력학회 2015 Nuclear Engineering and Technology Vol.47 No.3
Zirconium alloys are widely used in nuclear reactors as structural materials. During the operation, they are exposed to fast neutrons. Ion irradiation is used to simulate the damage introduced by neutron irradiation. In this article, we briefly review the neutron irradiation damage of zirconium alloys, then summarize the effect of ion irradiation on microstructural evolution, mechanical and corrosion properties, and their relationships. The microstructure components consist of dislocation loops, second phase precipitates, and gas bubbles. The microstructure parameters are also included such as domain size and microstrain determined by X-ray diffraction and the S-parameter determined by positron annihilation. Understanding the relationships of microstructure and properties is necessary for developing new advanced materials with higher irradiation tolerance.
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Behavior and Mechanism of Void Welding Under Thermal Mechanical Coupling
Fei Chen,Xitao Wang,Huiqin Chen,Shue Dang 대한금속·재료학회 2022 METALS AND MATERIALS International Vol.28 No.7
Shrinkage cavity, microporosity, blowhole and the likes are the typical void defects in ingot. Only through reasonable hightemperature deformation and heat preservation process can the void defects be closed and welded to ensure the high qualityof forgings. However, there are few researches on the welding behavior of voids, and the understanding of the void weldingmechanism is still insufficient. In order to further study the welding behavior of void and explore the welding mechanism,the welding process of void and microstructure evolution around void under thermal mechanical coupling were studied byphysical simulation. The results show that heating temperature, holding time, plastic deformation play an important role invoid welding. The void welding degree increases with the increase of heating temperature, holding time and plastic deformation. Besides, there are three main welding mechanisms for void defects, including the volume of microvoids decreasesdue to vacancy diffusion, the void welding mechanism caused by the austenite-ferrite transformation at lower temperaturesand the void welding mechanism caused by recrystallization and grain growth of austenite grains at higher temperatures.
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Chunye Lin,Jing Wang,Shaoqing Liu,Mengchang He,Xitao Liu 한국지질과학협의회 2013 Geosciences Journal Vol.17 No.4
The quantitative contamination assessment of toxic elements in sediments is a challenge due to the lack of their geochemical background or baseline levels and sediment heterogeneity. Eighty-eight sediment samples were collected in the Liao River Watershed (LRW) and analyzed for Co, Mn, V, Sc, Fe, Al, and sediment properties. The average background levels, geochemical baseline levels (GBL), and geochemical baseline functions of Co,Mn, and V in the sediments were obtained using statistical and geochemical methodologies. The concentrations of Co, Mn, and V were 0.86 to 23.40, 105.9 to 1771.6, and 6.47 to 153.30 mg/kg, respectively. The average background levels and GBLs were 7.2 and 14.4mg/kg for Co, 422 and 762 mg/kg for Mn, and 35.4 and 59.0 mg/kg for V. The linear correlation of Co, Mn, and V with particle-size proxy elements (normalizers) Sc, Fe, and Al was statistically significant with probability (p-value) <0.001 level, showing that Fe,Al, and Sc can be used as particle-size proxy elements to develop the GBFs of Co, Mn, and V. The spatial distribution of the sampling sites with the concentrations of Co, Mn, and V either outlied or greater than GBLs may be related to industry and mine distribution,showing the impact of human activities on the contents of Co, Mn, and V in the LRW sediments. The procedure in the study can be used to estimate GBLs and construct GBFs of toxic elements in other watershed sediments on the world in order to manage sediment quality. The quantitative contamination assessment of toxic elements in sediments is a challenge due to the lack of their geochemical background or baseline levels and sediment heterogeneity. Eighty-eight sediment samples were collected in the Liao River Watershed (LRW) and analyzed for Co, Mn, V, Sc, Fe, Al, and sediment properties. The average background levels, geochemical baseline levels (GBL), and geochemical baseline functions of Co,Mn, and V in the sediments were obtained using statistical and geochemical methodologies. The concentrations of Co, Mn, and V were 0.86 to 23.40, 105.9 to 1771.6, and 6.47 to 153.30 mg/kg, respectively. The average background levels and GBLs were 7.2 and 14.4mg/kg for Co, 422 and 762 mg/kg for Mn, and 35.4 and 59.0 mg/kg for V. The linear correlation of Co, Mn, and V with particle-size proxy elements (normalizers) Sc, Fe, and Al was statistically significant with probability (p-value) <0.001 level, showing that Fe,Al, and Sc can be used as particle-size proxy elements to develop the GBFs of Co, Mn, and V. The spatial distribution of the sampling sites with the concentrations of Co, Mn, and V either outlied or greater than GBLs may be related to industry and mine distribution,showing the impact of human activities on the contents of Co, Mn, and V in the LRW sediments. The procedure in the study can be used to estimate GBLs and construct GBFs of toxic elements in other watershed sediments on the world in order to manage sediment quality.
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Ti, Wenxin,Wu, Huanchun,Xue, Fei,Zhang, Guodong,Peng, Qunjia,Fang, Kewei,Wang, Xitao Korean Nuclear Society 2021 Nuclear Engineering and Technology Vol.53 No.8
The effect of thermal aging at 475 ℃ and 750 ℃ of Z3CN20.09M cast duplex stainless steel (CDSS) on microstructure, mechanical and intergranular corrosion properties were investigated by transmission electron microscope (TEM), nano indenter, scanning electron microscope (SEM) and corrosion fatigue test system. The result indicated that the spinodal decomposition and G precipitated were occurred after aged at 475 ℃, as well as sigma precipitated at 750 ℃. The microstructure degeneration of ferrite was saturated after aged for 2000h and 200 h at 475 ℃ and 750 ℃ respectively. The mechanical properties, intergranular corrosion resistance and corrosion fatigue lives were continuing deteriorated with increasing the aging time at both temperatures. The difference of the degeneration mechanisms of Z3CN20.09M CDSS aged at 475 ℃ and 750 ℃ was analyzed.
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